Comparative Study of Physical Models for Particle Sedimentation Using SIMMER Code
- 1. CEA, DES, IRESNE, DER, F-13108 St Paul Les Durance, (France)
- 2. CEA, DES, IRESNE, DEN, F-13108 St Paul Les Durance, (France)
- 3. CNRS, IN2P3, LPSC Grenoble INP, F-38026 Grenoble, (France)
Description
In the context of improved safety requirements for Generation IV sodium-cooled fast reactors (SFR), an innovative severe accident mitigation scenario is being investigated. In the French frame of SFR research, the mitigation strategy consists of transfer tubes and a core catcher. The transfer tubes are dedicated to discharge molten fissile materials from the core center region and to guide them toward the core catcher where long-term cooling and subcritical state may be assured. The physical phenomena occurring during the discharge process are introduced in this paper. The current demonstration of the mitigation strategy uses best-estimate calculations with the reference computer code SIMMER. Previous analyses showed that the material discharge through the transfer tubes might be efficient; however, uncertainties of SIMMER approach are identified on the molten material mobility during the relocation process. It is related to a blockage formation due to particulate solid debris accumulation inside the transfer tube, in case of low energy accumulation in the degraded fuel, is believed to originate from the solid particle treatment in the code. As the performance of mitigation strategy strongly depends on the mobility of the relocating mixture, the most predictive behavior of particle flows is of great importance to SFR safety. Therefore, the SIMMER modeling of such flows is analyzed in this work. The first verification and validation test cases regarding the gravitational settling of particle clouds at varying volume fractions are presented. Recommendations for reactor calculations and first orientations for future research and development are highlighted. (authors)
Additional details
Identifiers
- DOI
- 10.1115/1.4049197;
Publishing Information
- Journal Title
- Journal of Nuclear Engineering and Radiation Science
- Journal Volume
- 7
- Journal Issue
- no.4
- Journal Page Range
- p. 041601.1-041601.11
- ISSN
- 2332-8983
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 55070588
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S97: MATHEMATICAL METHODS AND COMPUTING;
- Descriptors DEI
- COOLING SYSTEMS; CORE CATCHERS; EXCURSIONS; FAST REACTORS; FISSILE MATERIALS; GUIDE TUBES; MELTDOWN; MITIGATION; NUCLEAR FUELS; REACTOR SAFETY; SAFETY; SIMULATION; SODIUM COOLED REACTORS; TUBES; VALIDATION; VERIFICATION
- Descriptors DEC
- ACCIDENTS; BEYOND-DESIGN-BASIS ACCIDENTS; ENERGY SOURCES; ENERGY SYSTEMS; EPITHERMAL REACTORS; FISSIONABLE MATERIALS; FUELS; LIQUID METAL COOLED REACTORS; MATERIALS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SAFETY; SEVERE ACCIDENTS; TESTING; TUBES
Optional Information
- Notes
- 36 refs.